Transient dryout prediction using a computationally efficient method for sub-channel film-flow analysis

被引:11
作者
Adamsson, C. [1 ,2 ]
Le Corre, J. M. [2 ]
机构
[1] Vattenfall Nucl Fuel, Stockholm, Sweden
[2] Westinghouse Elect, Vasteras, Sweden
关键词
CRITICAL HEAT-FLUX; ANNULAR-FLOW; MODEL; VALIDATION; CODE; POWER;
D O I
10.1016/j.nucengdes.2014.09.012
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A simplified three-field sub-channel model for prediction of dryout in BWR fuel assemblies under steady-state as well as transient conditions is presented. Fast and robust calculations are achieved by decoupling the conservation equations for the liquid film from the solution of the sub-channel problem, which relies on a traditional two-field model. The liquid films, which are attached to various walls can then be analyzed as a post-process, effectively extending the two-field sub-channel code to a three-field code. The model has been validated with thousands of steady-state and hundreds of transient dryout measurements in full-scale fuel-bundle mock-ups under realistic conditions. The results show that it is possible to predict the dryout power with a standard deviation of about 4% for both steady-state and transient conditions using only a minimum of model calibration to account for details in the spacer grid design. (C) 2014 Elsevier B.V. All rights reserved.
引用
收藏
页码:316 / 325
页数:10
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